EP2681743A1 - Procede de precipitation d'un ou plusieurs solutes - Google Patents
Procede de precipitation d'un ou plusieurs solutesInfo
- Publication number
- EP2681743A1 EP2681743A1 EP12707502.6A EP12707502A EP2681743A1 EP 2681743 A1 EP2681743 A1 EP 2681743A1 EP 12707502 A EP12707502 A EP 12707502A EP 2681743 A1 EP2681743 A1 EP 2681743A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- liquid phase
- reactor
- mixture
- phase
- solute
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/10—Processing by flocculation
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Definitions
- the invention relates to a method for precipitating one or more solutes contained in a liquid phase.
- the process for treating spent nuclear fuel may comprise, after the conventional steps of stripping and dissolving in concentrated nitric acid, several purification cycles, and in particular three cycles, namely:
- a first cycle that aims to jointly decontaminate uranium and plutonium vis-à-vis two actinides (111), americium and curium, as well as most of the fission products, and to achieve a partition uranium and plutonium in two streams;
- second cycle uranium and “second cycle plutonium” and which aim to purify uranium and plutonium separately after their partition.
- the plutonium thus isolated is then subjected to an oxalic precipitation step, to give a plutonium oxalate precipitate PU (C 2 O 4 ) 2A, which precipitate can then be converted into plutonium oxide.
- Reactors of simple design may be crystallizer type reactors and vortex type reactors.
- the crystallizer-type reactors are based on the principle of a gradual increase in the supersaturation of the precipitation solution generating a crystallization of the solute to be precipitated, this type of reactor conventionally operating in a batch mode, which limits their use in the optical system. to make a precipitation on an industrial scale.
- one solution is to multiply the reactors and operate them in parallel and shifted.
- Vortex type reactors as defined, for example, in US 395,988 and US 4,464,341, are conventionally constituted of a glass container whose contents are agitated by the rotation of a bar inside, which creates a vortex with the dual function of confining, within an aqueous phase, the precipitate away from the glass walls and to guarantee a sufficient residence time to allow the growth of the grains of the precipitate, in order to make it less tights.
- these reactors are subject to periodic fouling and it is difficult to predict for them the guarantee of a subcritical regime when one wants to increase the dimensions of these reactors.
- the invention relates to a method for precipitating at least one solute in a reactor comprising:
- step b) a step of fluidization by the third phase of the mixture mentioned in step a).
- the method of the invention has the following advantages:
- the method of the invention comprises a first step a) of contacting in co-current in a reactor a first liquid phase comprising the solute, a second liquid phase comprising a solute precipitation reagent, whereby a mixture is obtained comprising, in suspension, precipitate particles, and a third liquid phase constituting a dispersing phase for said mixture.
- the first liquid phase and the second liquid phase are miscible with each other, while the third liquid phase is immiscible with the mixture comprising the first liquid phase and the second liquid phase.
- the first liquid phase, the second liquid phase and the third liquid phase may be injected into a reactor, for example, at a lower part thereof, this lower part constituting an injection zone.
- the inlet of the first liquid phase and the inlet of the second liquid phase may be arranged at the same height of the injection zone and located opposite each other, by means of which, during the injection simultaneous of these two phases, the contacting of these two phases is instantaneous thus spontaneously forming a mixture comprising, in suspension, the precipitate particles.
- the inlet of the latter can be located in the injection zone at a height lower than that of the entrances of the first liquid phase and the second liquid phase.
- the first liquid phase, the second liquid phase and the third liquid phase can be injected into a reactor, for example, at an upper part thereof, this upper part constituting an injection zone.
- the inlet of the first liquid phase and the inlet of the second liquid phase may be arranged at the same height of the injection zone and located opposite each other, by means of which, during the injection simultaneous of these two phases, the contacting of these two phases is instantaneous thus spontaneously forming a mixture comprising, in suspension, the precipitate particles.
- the inlet of the latter can be located, in the injection zone, above the entrances of the first liquid phase and the second liquid phase.
- the injection of the first liquid phase, the second liquid phase and the third liquid phase can be performed in continuous mode or in semi-continuous mode, which means, for the latter case, that at least one of the aforementioned liquid phases is injected in continuous mode and at least one of the aforementioned liquid phases is injected discontinuously (for example, by periodic injection of the slot type, ramp type or Dirac type).
- dispersant phase it is meant that the third liquid phase is capable of causing the mixture formed by bringing the first liquid phase into contact with the second phase. liquid in which precipitate is formed or dispersed in the form of drops in the third liquid phase, this third liquid phase being generally chosen so as to be immiscible with the mixture resulting from the first liquid phase and the second liquid phase.
- the contacting step a) is carried out conventionally by injection of a first liquid phase, a second liquid phase and a third liquid phase in a specific reactor zone, for example a lower part of said reactor ( said injection zone) or an upper part of said reactor, knowing that the feed rate for the third liquid phase should preferably be greater than that of the first liquid phase and / or the second liquid phase, so that the third liquid phase can ensure the fluidization of the mixture resulting from the first liquid phase and the second liquid phase.
- the choice of such a feed rate for the third liquid phase will allow, in addition, the precipitated grains formed by reaction between the first phase and the second liquid phase not to adhere to the walls of the reactor.
- step a the first liquid phase and the second liquid phase will react with each other to form a mixture comprising a precipitate of the solute, which mixture will be entrained by the third liquid phase in a fluidized bed regime (corresponding to the above-mentioned step b) and also referred to as fluidization).
- fluidization it is meant to suspend drops loaded with precipitate particles formed in an ascending fluid flow, said charged droplets of particles constituting the fluidized bed and the ascending fluid flow being constituted by the third phase. liquid.
- the process may comprise a sedimentation step of the mixture resulting from step b), this sedimentation step can be carried out by simple decantation, this sedimentation step being followed by a step of collection of said precipitate.
- the collection step can be typically performed by withdrawing the sediment precipitated particles. This collection may be followed by solid-liquid separation operations such as filtrations, centrifugations or other, so as to rid the precipitate particles of the liquid phase that may have been withdrawn with them, as well as washing operations and / or drying.
- solid-liquid separation operations such as filtrations, centrifugations or other
- the method of the invention may further comprise a step of recycling the third phase liquid, which can be reinjected at the injection zone mentioned above.
- the process of the invention is advantageously carried out, especially in the case where the density of the mixture of the first liquid phase and the second liquid phase is greater than that of the third liquid phase, in a fluidized bed reactor.
- vertical main axis comprising:
- an upper part also called upper part devoted to the sedimentation of the precipitate formed.
- vertical main axis comprising:
- an upper part also called upper part devoted to the injection of the first liquid phase, the second liquid phase and the third liquid phase
- the precipitate formed in the context of this process is an actinide oxalate precipitate (s).
- the first liquid phase is, conventionally, an aqueous solution comprising, as solute, at least one actinide element (this solution being hereinafter referred to as "actinide solution (s)";
- the second liquid phase is, conventionally, an aqueous solution comprising a precipitation reagent of the actinide element or elements present in the first liquid phase, this precipitation reagent being oxalic acid (this solution being hereinafter referred to as "oxalic solution”); ); and
- the third liquid phase is, conventionally, an organic solution comprising an immiscible organic solvent with the first liquid phase and the second liquid phase, this organic solvent possibly being hydrogenated dodecane or tetrapropylene (known by the abbreviation TPH).
- the actinide solution (s) conventionally contains the actinide (s) in the form of nitrate (s), as it is in this form that these elements are generally produced by spent nuclear fuel treatment plants.
- the actinides involved may be uranium, plutonium, neptunium, thorium, americium and / or curium.
- it may be uranium, plutonium, neptunium, americium and / or curium, when the precipitates of oxalates formed are intended to be converted into an actinide compound (s) useful for the manufacture of nuclear fuel pellets, of the oxide, carbide or nitride type.
- Fig. 1 is a diagram illustrating a suitable reactor for the preparation of a cerium oxalate precipitate according to the process of the invention.
- FIG. 2 is a diagram illustrating in detail the lower part of the reactor (constituting the injection zone) illustrated in FIG.
- Figures 3 to 5 correspond to images taken at the intermediate portion of the reactor (first vertical portion) for different modes of operation described in the example below.
- reactor 1 To carry out tests relating to the precipitation of cerium oxalate, reactor 1 is used, which is shown schematically in FIG.
- This glass reactor of vertical main axis consists of three parts:
- a lower part 3 constituting the injection zone of the first liquid phase consisting of an aqueous solution comprising cerium in the form of cerium nitrate, the second liquid phase consisting of an oxalic solution and the third liquid phase consisting of organic solution of hydrogenated tetrapropylene, this lower part being shown in detail in FIG. 2;
- this intermediate part consisting of a cylindrical tube comprising a first vertical part 7 with a constant cross section ( 15 mm in diameter) which has a curvature 9 and a second vertical portion 11;
- an upper part 13 devoted to the sedimentation recovery of the precipitate formed, consisting of a settler, into which the open end of the second vertical portion 11 of the tube constituting the intermediate part of the reactor is immersed.
- the lower part shown in detail in FIG. 2, consists of a cylindrical tube of constant circular section (15 mm in diameter) closed at its lower end 15.
- the reagents that is to say the hydrogenated tetrapropylene organic solution (constituting the third liquid phase), the solution comprising cerium (constituting the first liquid phase) and the oxalic solution (constituting the second liquid phase), are introduced in this lower part via:
- a vertical nozzle 17 passing through the lower end of the tube and supplying the lower part of the reactor with organic solution via a valve 18;
- these nozzles 19 and 21 located halfway up the injection zone and diametrically opposed to each other, these nozzles 19 and 21 consisting of a horizontal glass tube starting from its entry and ending under bent shape at the outlet (corresponding to that part of the nozzle which enters the lower part of the reactor), these nozzles supplying the lower part of the reactor respectively in oxalic solution and in solution comprising cerium.
- the lower part 3 of the reactor is also provided, at its lower end, with a cannula 23 for purging the reactor, this cannula being connected to a pipe 25 provided with a valve 27.
- the vertical nozzle 17 is connected to a feed tank 29 in organic solution via a pipe 31 provided with a pump 33 for adjusting the feed rate of the organic solution.
- the nozzles 19 and 21 are, respectively, connected to an oxalic solution supply tank 35 and a solution supply tank comprising cerium 37 via lines 39 and 41 also provided with pumps 43 and 45 and valves 47 and 49, which will allow to adjust the feed rate of the oxalic solution and the solution comprising cerium.
- the reactor does not comprise an agitator, the mixture of the different phases being provided solely by the feed rates of this reactor in these different phases.
- the intermediate portion consists of a vertical cylindrical tube with a constant cross-section (15 mm in diameter), which extends the constituent tube of the lower part of the reactor, over a height of 1 m (thus constituting a first vertical part), beyond which this tube has a curvature leading to a second vertical part whose end plunges into the part top of the reactor, the tube retaining the same section over its entire length.
- the upper part 13 of the reactor consists of a decanter having a grid 51 making it possible to force the coalescence of the fines (corresponding to the very fine droplets) which can be entrained by the organic solution during the decanting operation, an outlet 53 provided with a valve 55 in its narrowed lower part allowing the evacuation of the precipitate and may also constitute a purge line of the decanter and an outlet 57 provided with a valve 59 for the evacuation of oxalic mother liquors.
- the decanter also comprises an overflow 61 allowing the entire organic phase to be re-routed to the organic phase reservoir 29 via a pipe 63.
- A, B and C Three tests (respectively A, B and C) were carried out in a sticky precipitation condition from a first liquid phase (an aqueous nitrate solution (1.5 N) of cerium nitrate having a concentration of 24 g / L). a second liquid phase (an aqueous oxalic solution having a concentration of 0.7 mol / L) and a third liquid phase (an organic hydrogenated tetrapropylene TPH solution).
- the first test A is carried out with the following liquid phase flow rates:
- the second test B is carried out by decreasing the flow rate of the organic phase relative to the test A, the respective flow rates of the liquid phases being as follows:
- the third test C is carried out by further decreasing the flow rate of the organic phase relative to the test B, the respective flow rates of the liquid phases being as follows: * 0.4 L / h of cerium (III) nitrate;
- This latter mode is particularly interesting because it makes it possible to obtain a stable confinement of the precipitate clusters by the organic solution and a long residence time in the reactor.
- this mode of operation makes it possible to absorb feed rates in the first liquid phase (that comprising cerium nitrate) relatively high.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
Abstract
Description
Claims
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR1151610A FR2971948B1 (fr) | 2011-02-28 | 2011-02-28 | Procede de precipitation d'un ou plusieurs solutes |
| PCT/EP2012/053134 WO2012116930A1 (fr) | 2011-02-28 | 2012-02-24 | Procede de precipitation d'un ou plusieurs solutes |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP2681743A1 true EP2681743A1 (fr) | 2014-01-08 |
| EP2681743B1 EP2681743B1 (fr) | 2014-11-12 |
Family
ID=45808802
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP20120707502 Active EP2681743B1 (fr) | 2011-02-28 | 2012-02-24 | Procede de precipitation d'un ou plusieurs solutes |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US9472312B2 (fr) |
| EP (1) | EP2681743B1 (fr) |
| JP (1) | JP6054313B2 (fr) |
| FR (1) | FR2971948B1 (fr) |
| WO (1) | WO2012116930A1 (fr) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP7102221B2 (ja) * | 2018-05-16 | 2022-07-19 | 株式会社東芝 | 放射性廃水処理装置、および、放射性廃水処理方法 |
Family Cites Families (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US395988A (en) | 1889-01-08 | Car-coupling | ||
| BE653109A (fr) * | 1963-09-19 | |||
| FR2511267A1 (fr) | 1981-08-12 | 1983-02-18 | Commissariat Energie Atomique | Appareil a vortex pour la fabrication d'un precipite |
| US4548790A (en) * | 1983-07-26 | 1985-10-22 | The United States Of America As Represented By The United States Department Of Energy | Method for extracting lanthanides and actinides from acid solutions |
| JP2007044678A (ja) * | 2005-08-12 | 2007-02-22 | Canon Inc | 化学反応実施方法 |
| FR2905283B1 (fr) * | 2006-08-31 | 2009-04-17 | Commissariat Energie Atomique | Procede et dispositif de precipitation d'un solute |
| US20100301287A1 (en) * | 2006-09-08 | 2010-12-02 | Ch2M Hill, Inc. | Process for Treating Spent Nuclear Fuel |
| WO2008105928A2 (fr) * | 2006-09-08 | 2008-09-04 | Michael Ernest Johnson | Procédés pour traiter des compositions contenant de l'uranium et du plutonium |
| JP5193687B2 (ja) * | 2008-05-30 | 2013-05-08 | 株式会社東芝 | 使用済み燃料再処理方法 |
| JP5683796B2 (ja) * | 2009-07-13 | 2015-03-11 | 株式会社Kri | 微小構造体の製造方法およびマイクロリアクター |
-
2011
- 2011-02-28 FR FR1151610A patent/FR2971948B1/fr not_active Expired - Fee Related
-
2012
- 2012-02-24 EP EP20120707502 patent/EP2681743B1/fr active Active
- 2012-02-24 US US14/000,253 patent/US9472312B2/en active Active
- 2012-02-24 WO PCT/EP2012/053134 patent/WO2012116930A1/fr not_active Ceased
- 2012-02-24 JP JP2013555828A patent/JP6054313B2/ja not_active Expired - Fee Related
Non-Patent Citations (1)
| Title |
|---|
| See references of WO2012116930A1 * |
Also Published As
| Publication number | Publication date |
|---|---|
| US9472312B2 (en) | 2016-10-18 |
| JP2014514133A (ja) | 2014-06-19 |
| FR2971948B1 (fr) | 2013-03-29 |
| WO2012116930A1 (fr) | 2012-09-07 |
| US20140044616A1 (en) | 2014-02-13 |
| EP2681743B1 (fr) | 2014-11-12 |
| JP6054313B2 (ja) | 2016-12-27 |
| FR2971948A1 (fr) | 2012-08-31 |
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